BUILDUP OF FISSION PRODUCTS IN REACTOR FUEL AND COOLANT WITH 'UNCLAD' FUEL MATERIAL

Technical Report · Wed Oct 18 00:00:00 EDT 1961

DOI:https://doi.org/10.2172/4807349· OSTI ID:4807349

Cottrell, W B; Mann, L A

Concentrations of fission products in the fuel and in the coolant stream of a generalized reactor power plant employing unclad fuel material were calculated using actual fission-product chains and wide ranges of assumed values of escape rate from the fuel and removal rate from the coolant stream. The calculations were made on an IBM 704 digital computer. Some typical results are displayed in the form of graphs to illustrate the effects of the variables. As data on escape rates from fuel and removal rates from coolant become available, the tables and graphs developed by this study can be used to estimate the fissionproduct concentration in the coolant stream, which would in turn furnish a basis for determining the degree of coolant purification required to maintain the circulating activity below a given level. (auth)

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• NSA Number: NSA-16-004989
• OSTI ID: 4807349
• Report Number(s): ORNL-TM-66
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-62
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
COMPUTERS
CONTAMINATION
COOLANT LOOPS
COOLANTS
DECAY
DECONTAMINATION
DIAGRAMS
EQUATIONS
FISSION PRODUCTS
FISSIONABLE MATERIALS
FUEL ELEMENTS
FUELS
IBM 704
IMPURITIES
IRRADIATION
NUMERICALS
POWER PLANTS
PROGRAMMING
RADIATION DOSES
RADIOACTIVITY
REACTOR CORE
REPROCESSING
TABLES
THERMAL DIFFUSION